ML110620007

Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2009 Refueling (RF-18) Outage

ML110620007
Person / Time
Site:	Summer
Issue date:	03/07/2011
From:	Martin R Plant Licensing Branch II
To:	Gatlin T South Carolina Electric & Gas Co
Martin R, NRR/DORL, 415-1493
References
TAC ME4038
Download: ML110620007 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 7, 2011 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1, REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE FALL 2009 REFUELING (RF-18) OUTAGE (TAC NO. ME4038)

Dear Mr. Gatlin:

By letter dated June 1, 2010 (Agencywide Documents Access and Management System Accession No. ML101540064), South Carolina Electric & Gas (SCE&G), the licensee, submitted information summarizing the results of the 2009 steam generator (SG) tube inspections at Virgil C. Summer Nuclear Station, Unit No.1 (VCSNS).

VCSNS has three Westinghouse Delta-75 replacement SGs containing 6,307 thermally treated Alloy 690 tubes with an outside diameter of 0.6875 inches and a nominal wall thickness of 0.040 inches. Stress relief was performed during fabrication on the U-bends of the first 17 rows of tubing. The straight sections of tubing are supported by nine tube support plates made of 1.125 inches thick, SA-240, Type 405 stainless steel.

The licensee provided the scope, extent, methods, and results of the SG tube inspections in the document referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.

T. Gatlin -2 Based on a review of the information provided, the Nuclear Regulatory Commission (NRC) staff concludes that the licensee provided the information required by the technical specifications. In addition, the NRC staff concludes that there are no technical issues that warrant a follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.

Sincerely, V"

/4;;;/ /l1.wtJ'J "Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395 cc: Distribution via Listserv

ML110620007 OFFICE NRR/LPL2-1/PM NRRlLPL2-lILA tr"CSGB/BC NRRILPL2-1/BC NRRlLPL2-1/PM NAME RMartin MO'Brien Taylor GKulesa RMartin DATE 317111 3/7/11 01119/11 317111 317111